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Microstructural and microchemical characterization of irradiated pressure vessel steels

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5789982
; ; ; ;
None
Research Organization:
Westinghouse Electric Corporation, Research and Development Center, 1310 Beulah Road, Pittsburgh, PA 15235
OSTI ID:
5789982
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHEMICAL COMPOSITION
COMPARATIVE EVALUATIONS
CONTAINERS
DAMAGING NEUTRON FLUENCE
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALLURGY
MORPHOLOGICAL CHANGES
NEUTRON FLUENCE
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STEELS
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE